JP0450105 the SMORES Capability for Minimum Critical Mass

Total Page:16

File Type:pdf, Size:1020Kb

JP0450105 the SMORES Capability for Minimum Critical Mass JAERI-Conf 2003-019 JP0450105 The SMORES Capability for Minimum Critical Mass Determination Y. KARNf, D. REGEV, E. GREENSPAN' I,S. GOLUOGLL, L.M. PETRIE'and C.M HOPPER' Uni"rsity of California,Berkeley, California94720-1730, USA 2Oak Ridge National Laboratory,P. 0. Box 2008, Oak Ridge, Tennessee 3 7831-6370, USA The purpose of the present work is to illustrate the capability of SMORES - a nw sequence incorporated in SCALE-5, for automated minimurn critical mass (MCM) determination. The illustration Ls de by identilytrig the MCM of spherical systems of "U, U or "Pu moderated and reflected with either D20 or a combination of polyethylene and Be. he latta povide the lowest critical mm of, respectively, 151.7 g, 202.2 g and 119.0 g. These masses are close to a factor of 2 lower than the MCM of the corresponding fissile material with D20 and close to a factor of 4 for the MCM H20. The fissile material concentration exhibit a spike rim the core outer boundary at the interface between the poyethylene a Be. The SMORES sequence of SCALE could be useful fbr determining margins of subcriticality and for oer applications encountered by tic criticality safety cmmunity. KEYWORDS: SMORES; SCALE, Minimum CriticalMass; Maximum ke 233 U; 235 U; 239p" 1. Introduction search for the minimum crfical mass or for the minimum mass that can provide a pecified k < .0. A new prototypic analysis sequence, SMORES The ppose of the pesent work is to illustrate the (Scale Material Optimizanori and REplacement capability of the new SCALE sequence fb mmum Sequence), was - recently developed for critical mass MCM) determination. incorpoation into the SCALE-5 code package'). The illustration is done by appyirig the SMORES SMORES, provides for a semi-automatic search for sequence to determine the MCM of two types of either the maximinn kff of a given amount of systems: (A) A system consisting of a single fissile specified fissfle material, or the mmum critical material moderated and reflected by heavy-water and mass. It is described in detail in reference 2 and also M A system consisting of a singje fissile material in references 3 4 and 5. combination with two moderating materials - Very briefly, the search procedure proceeds as poyethylene (Poly) and berylliurn (Be). fbllows: Befbre starting the optimization process, a Type A systems were found by previous researchers rekrence system is defined This oxides the core to offer the lowest MW of a given fissile material radio or thickness and cposition and reflector when in combination with a sgle rnoderating/reflecting thickness and composition. Using firA order material. 7-9) T B systems were considered in a perturbation theory Equal Volurne Replacement previous tu;r)bt considered only 29pU fissk isotope Reactivity Worth (EVRRW) traverses are calculated and used infinit dution au&sections. for a system consdacm the com on of wch The following illustrations pertain to problems is a design variable. An EVRRW of material i with characterized by a sle fel aterial. Recently, the respect to refmnce material I is the reactivity effect SMORES capability has been expanded4) to enable search of rlacing a cubic centimetm of matenal I by the fbr maximum kr for Pstems with any number of fuel same volume of material For minimurn critical and non-fuel constituents. he ew capability Ls riot mm problems the EVRRW guide an automated incorporated, yet, within SCALE. redistribution of the systern conskmts so as to many= the fjel inventory while keeping k at or 2. Mustrations very close to .0. The optimization process is iterative, it proceeds until the EVRRW distribution 2.1 MCM in D20 of the fuel becomes flat Mass the core and is lower The systems considered are 240 cm i rius spherm outside of the core. of D20 with several hundred gms of a fissile material. SMORES can be used to determine margins of The fissile material is initially unilbrmly distributed submticality by identilying the maximum value of over a central sphere that is 60 cm in drus. The sphere the effective multiplication factor, km that can is divk1ed into 120 half-centimeter-thick zones he result from a given mass of a given fissile aterial composition aoss a zone is constant The optimization when combination with specified moderating ad variable is the concentration of the fissile material reflecting materials. The identification of kmdr is each of the zones. accomplished sernimautornatically, using the Figure I illustrates the opfirrial ontration of J optimization strategy of the SWAN Code4fi). in practically finft D medium. The MCM is found Alternatively, SMORES can perform an automated to be 344.84 g 2 U. Te uranium occupies the CorrespondingauthorTel. 001-510-643-9983,Fax. +001-510-643-9685,E-niail: gehudnuc.berkeley.edu 55 - JAE RI - Conf 2003-019 innermost 32 cm spherical region, and its 4.OE-0-4 - concentration monotonously increases towards the center. Figure 2 shows the EVRRW distribution two successive iterations contending to the 23.OE-04 - optimal systern composition It is seen that do effectiveness fiinctiori Ls practimfly flat across the U. zones that contain 131U and is lower in a o OE2.OE-04 zones This distribution unplies that the arrived at .20 compositiori Ls the optimal; no shuffling of constituents can finther increasekr 1.OE-04 C%1 4.OE-04 O.OE+00 0 10 20 30 40 50 60 c 2 3.OE-04 Radius (cm) U. Optimal 3 diStnbUfion in D yielding 11 Fig. 3 minimurn critical mass of 295.60 g. R 4.DE-04 I.OE-04 ....... 0 3.OE-04 O.OE+00 0 10 20 30 40 50 60 U. Radius (cm) 0 E2.OE-04 Mg I Optima 1211U dis:iribution in O yielding minimum critical ass of 344.84 g. 1.OE-04 Of 0.022 - O.OE+00 f......... ...... ........ 0.018, 0 10 20 30 40 50 60 Radius (cm) 0.014 - 0.010 Fig. 4 Optimal 139pU distribution in D yielding minimum critical mass of2O4.24 g. 0.006 .... .... 1 0 10 20 30 40 50 60 4.OE-04 - Radius (cm) c .2 'U 3.OE-04 - Fig. 2 Equal Volume RepLacement Reactivity LL Worth traverses in successive iterations 'El 2.OE-04 - cotirsponding t the optimal composition of Fig. 1. .2 0 A similar analysis done for otha fissile materials IL 1.OE-04 for 2 g for 239pU resulted in 295.60 J, 204.24 and 135.96 g for 41pLL Te geral shape of the fissile rnaterial distribution Ls similar t that of O.OE+00 Figure I but the core radius and the peak 0 10 20 30 40 50 60 concentration are fissile nuiterial dependent Fgure Radius (cm) 3 shows the optimal composition of 233U in DD while Figure 4 shows the optimal 239 Pu-1320 system Optimal 241pU distribution and Figure shows the optimal 241Pu-D20 system. Fi.g.5 in D20 yielding minimum critical mass of 135.96 g. - 552 - JAERI-Conf 2003-019 The esults for the 239pU - DP system can be Figur 9 shows the effect of zone thickness on the compared with results orted by Yatdl. The optimal 2 &tnbUfiorL The mum Critical mass minimum critical mass at roorn temperature was value s practically the same for both zone ducknesses faind8 t be 390 g; it corrosponds to a thin shell of considered. Figures IO and I I show the corresponding 2N Pu flat Ls 50 cm in outer diameter and is polyethelene and berythurn optimal ffistribution. immersed in a 240 cm cube of D20. Heavy water Whereas the optimization using 0. c thick zones fiflS the 9pir Sphere interior a WeU. results in a complete separation between the two From the close to a factor of two difference in moderators, the optimization using the 025 cm zones the critical mass it appears that the optimal spatial results in a sght mixing of the two. diStribirtion of 29pU identified by SMORES is significantly more reactive than that of the spherical 6.OE-03 Al shell of eference S. In or to verify this hypothesis the SCALE sequence used for the 5.OE-03 - SMORES analysis was applied for calculating ker .2 of 240 cm in dius helical systems comprising of 4.01E-03 a sgle 204.24 g of shell with inside and U. outside the shelL Te maximum kr was found to r- 3.OE-03 - be 0883 - lower thari for the SMORES defined .0 core kf = 1.0). It corresponds to a shell that is 50 > 2.OE-03 - cm in outer diameter. Poly Be In order to verify the SMORES minimurn critical C4 1.0E-03 mass calculations reported above MCNP was applied to calculate k for the system compositions O.OE+00 reported in Figures I through 5. The MCNP 0.0 5.0 10.0 15.0 20.0 calcuhded kff is very close to unity for a fbur Radius (cm) systems, as can be seen from Table . Table I Comparison of MCNP Versus SMORES Fig. 6 Optimal 2sU distribution with polyethylene and Calculated kE Values for MCM in D20 berylhum. moderaturs/reflectors yielding minimum critical mass of 201.22 g. Fissile SMORES MCNPkr material ka 6.OE-03 A - - -BT- 0.999999 0.99722±0.00092 = U 1.000000 0.99871±0.00085 1.000013 0.99765±0.00089 5.OE-03 .2 PU 1.000048 1.00014±0.00096 4.OE-03 - U. 2.2 MCM In Polyethylene and Beryllium r 3.01E-03 - Figure 6 shows the optimal position of a 20 , - Poly Be Type spherical system composed of 23J, Poly > m 2.OE-03 and Be.
Recommended publications
  • Table 2.Iii.1. Fissionable Isotopes1
    FISSIONABLE ISOTOPES Charles P. Blair Last revised: 2012 “While several isotopes are theoretically fissionable, RANNSAD defines fissionable isotopes as either uranium-233 or 235; plutonium 238, 239, 240, 241, or 242, or Americium-241. See, Ackerman, Asal, Bale, Blair and Rethemeyer, Anatomizing Radiological and Nuclear Non-State Adversaries: Identifying the Adversary, p. 99-101, footnote #10, TABLE 2.III.1. FISSIONABLE ISOTOPES1 Isotope Availability Possible Fission Bare Critical Weapon-types mass2 Uranium-233 MEDIUM: DOE reportedly stores Gun-type or implosion-type 15 kg more than one metric ton of U- 233.3 Uranium-235 HIGH: As of 2007, 1700 metric Gun-type or implosion-type 50 kg tons of HEU existed globally, in both civilian and military stocks.4 Plutonium- HIGH: A separated global stock of Implosion 10 kg 238 plutonium, both civilian and military, of over 500 tons.5 Implosion 10 kg Plutonium- Produced in military and civilian 239 reactor fuels. Typically, reactor Plutonium- grade plutonium (RGP) consists Implosion 40 kg 240 of roughly 60 percent plutonium- Plutonium- 239, 25 percent plutonium-240, Implosion 10-13 kg nine percent plutonium-241, five 241 percent plutonium-242 and one Plutonium- percent plutonium-2386 (these Implosion 89 -100 kg 242 percentages are influenced by how long the fuel is irradiated in the reactor).7 1 This table is drawn, in part, from Charles P. Blair, “Jihadists and Nuclear Weapons,” in Gary A. Ackerman and Jeremy Tamsett, ed., Jihadists and Weapons of Mass Destruction: A Growing Threat (New York: Taylor and Francis, 2009), pp. 196-197. See also, David Albright N 2 “Bare critical mass” refers to the absence of an initiator or a reflector.
    [Show full text]
  • Reference Values for Nuclear Criticality Safety
    Nuclear Science ISBN 92-64-02333-X Reference Values for Nuclear Criticality Safety Homogeneous and Uniform UO2, “UNH”, PuO2 and “PuNH”, Moderated and Reflected by H2O A demonstration study by an Expert Group of the Working Party on Nuclear Criticality Safety for the OECD/NEA Nuclear Science Committee Final evaluation and report prepared by D. Mennerdahl (EMS, Sweden) Leading participants during the study W. Weber (GRS, Germany), Y. Naito (NAIS, Japan) and J. Anno (IRSN, France) Major organisations contributing with new calculation results EMS (Sweden), IPPE (Russia), IRSN (France), ORNL (US), Serco Ass. (UK) Reviewers of the final draft report include J.B. Briggs (INL), V. Rouyer (IRSN), S. Mitake (Japan), H. Okuno (Japan), Y. Rugama (OECD/NEA), R.M. Westfall (ORNL) © OECD 2006 NEA No. 5433 NUCLEAR ENERGY AGENCY ORGANISATION FOR ECONOMIC CO-OPERATION AND DEVELOPMENT ORGANISATION FOR ECONOMIC COOPERATION AND DEVELOPMENT The OECD is a unique forum where the governments of 30 democracies work together to address the economic, social and environmental challenges of globalisation. The OECD is also at the forefront of efforts to understand and to help governments respond to new developments and concerns, such as corporate governance, the information economy and the challenges of an ageing population. The Organisation provides a setting where governments can compare policy experiences, seek answers to common problems, identify good practice and work to co-ordinate domestic and international policies. The OECD member countries are: Australia, Austria, Belgium, Canada, the Czech Republic, Denmark, Finland, France, Germany, Greece, Hungary, Iceland, Ireland, Italy, Japan, Korea, Luxembourg, Mexico, the Netherlands, New Zealand, Norway, Poland, Portugal, the Slovak Republic, Spain, Sweden, Switzerland, Turkey, the United Kingdom and the United States.
    [Show full text]
  • Reactor Plutonium and Nuclear Explosives
    Reactor Plutonium Utility in Nuclear Explosives* Bruce T. Goodwin, PhD Associate Director-at-Large for National Security & Policy Research *drawn from the work of Robert Selden November 6, 2015 LLNL-PRES-801535 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344. Lawrence Livermore National Security, LLC Outline Bottom Line Up Front Plutonium Description Critical Mass Radioactivity & Heat Neutron Background A Nuclear Explosive Conclusions Summary Lawrence Livermore National Laboratory LL-NSO-U-2015-######_2 Bottom line up front • “A potential proliferating state or subnational group using designs and technologies no more sophisticated than those used in first-generation nuclear weapons could build a nuclear weapon from reactor grade plutonium that would have an assured, reliable yield of one or a few kilotons (and a probable yield significantly higher than that)” * • “An advanced nuclear weapon states such as the United States and Russia, using modern designs, could produce weapons from reactor grade plutonium having reliable explosive yields, weight, and other characteristics generally comparable to those of weapons made from weapons grade plutonium” * * Quoted from: US Department of Energy Publication “Nonproliferation and Arms Control Assessment of Weapons-Usable Fissile Material Storage and Excess Plutonium Disposition Alternatives, January 1997 http://www.osti.gov/scitech/biblio/425259 Lawrence Livermore National Laboratory LL-NSO-U-2015-######_3
    [Show full text]
  • Critical Mass Reduction
    LA-3651 . ULL- a 4’ LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS ● NEW MEXICO 1 k-——Critical Mass Reduction p.I 1--”— P- _—. I FORREFERENCE NOT TO BE TAKEN FROM THIS ROOM u,”mnv Wnuu CAT. NO. 1935 _ _— P ,-J UNITED STATES ATOMIC ENERGY COMMISSION CONTRACT W-7405 -ENG. 36 — s -., * LEGAL NOTICE This reportwas preparedas an accountof (governmentsponsoredwork. Neitherthe United States,northeCommhmion, nor any personactingon bebalfoftbeCommission: A. Makes any warrantyorrepresentation,expressedor implied,withrespecttotheaccu- racy,completeness,or usefulnessoftheinformationcontainedintbtsreport,or thattheuse of any information,apparatus,method,or processdtsclosedin tldsreportmay not infringe privatelyowned rights;or B. Assumes any liabilitieswttbrespecttotheuse of,or fordamages resultingfrom the useofany information,apparatus,method,or processdtsclosedinthisreport. As used in tbe above,“personacttngon bebalfof the Commission” includesany em- ployeeor contractorof theCommission,or employeeof such contractor,tothe extentthat such employeeor contractorof tbeCommission,or employeeof such contractorprepares, disseminates,or providesaccessto,any information~suant toMS employmentor contract withtheCommission,or bisemploymentwithsuchcontractor. This report expresses the opinionsof the author or authorsand does not necessarilyreflectthe opinions or views of the Los Alamos ScientificLaboratory. Printed in the United States of America. Available from Clearinghousefor Federal Scientificand TechnicalInformation NationalBureau of Standards,U. S. Department of Commerce Springfield,Virginia 22151 .Price: Printed Copy $ 3.00; Microfiche $0.65 .. -. LA-3651 UC-80, REACTOR TECHNOLOGY TID-4500 LOS ALAMOS SCIENTIFIC LABORATORY of the University of California LOS ALAMOS ● NEW MEXICO Report written: December 1, 1966 Report distributed:March 22, 1967 Critical Mass Reduction — -q by George A. Jarvis Carroll B. Mills ‘. .- -1- .. -. ABSTRACT A new low value for the critical mass of 23% in a critical.
    [Show full text]
  • T) M N M Japan Atomic Energy Research Institute (T 319-1195
    JAERI-Research JP0050827 2000-040 CRITICAL AND SUBCRITICAL MASSES OF CURIUM-245, -246 AND -247 CALCULATED WITH A COMBINATION OF MCNP4A CODE AND JENDL-3.2 LIBRARY September 2000 Hiroshi OKUNO and Hiromitsu KAWASAKI a * m =?• t) m n m Japan Atomic Energy Research Institute (T 319-1195 - ( T 319-1195 ;K«Lf,l-ffi«m?fcfJ- U ^^:f JjW'^P/'rIAJ) T^M'O' 1^ ± -5 •*f 'Mti * h This report is issued irregularly. Inquiries about availability of the reports should be addressed to Research Information Division, Department of Intellectual Resources, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun. Ibaraki-ken. 319-1195, Japan. © Japan Atomic Energy Research Institute, 2000 lift- WMi Li«; i-f)W'ftpfr JAERJ-Research 2000-040 Critical and Subcritical Masses of Curium-245, -246 and -247 Calculated with a Combination of MCNP4A Code and JENDL-3.2 Library Hiroshi OKUNO and Hiromitsu KAWASAKI* Department of Fuel Cycle Safety Research Nuclear Safety Research Center Tokai Research Establishment Japan Atomic Energy Research Institute Tokai-mura, Naka-gun, Ibaraki-ken (Received August 4, 2000) Critical masses of three curium isotopes, 245Cm, 246Cm and 247Cm, were calculated with a combination of the current version of the Japanese Evaluated Nuclear Data Library, JENDL-3.2, and a continuous energy Monte Carlo neutron transport code, MCNP4A. The subcritical masses corresponding to the neutron multiplication factor kejj = 0.9 and 0.8 were also computed in the same way. The subcritical masses that correspond to Kff~ 0.9 for 246Cm 246 metal and CmO2 with a 30-cm-thick stainless steel reflector were computed as 25.2 kg and 41.8 kg, respectively.
    [Show full text]
  • Some Effects of Pu-240, Pu-241, and Pu-242 on the Pu-239 Critical Mass of a Fast Reactor Frank Peter Mertes Jr
    Iowa State University Capstones, Theses and Retrospective Theses and Dissertations Dissertations 1962 Some effects of Pu-240, Pu-241, and Pu-242 on the Pu-239 critical mass of a fast reactor Frank Peter Mertes Jr. Iowa State University Follow this and additional works at: https://lib.dr.iastate.edu/rtd Part of the Nuclear Commons, and the Oil, Gas, and Energy Commons Recommended Citation Mertes, Frank Peter Jr., "Some effects of Pu-240, Pu-241, and Pu-242 on the Pu-239 critical mass of a fast reactor " (1962). Retrospective Theses and Dissertations. 2313. https://lib.dr.iastate.edu/rtd/2313 This Dissertation is brought to you for free and open access by the Iowa State University Capstones, Theses and Dissertations at Iowa State University Digital Repository. It has been accepted for inclusion in Retrospective Theses and Dissertations by an authorized administrator of Iowa State University Digital Repository. For more information, please contact [email protected]. This dissertation has been 63—2991 microfilmed exactly as received MERTES, Jr., Frank Peter. 1935— SOME EFFECTS OF PU-240, PU-241, AND PU-242 ON THE PU-239 CRITICAL MASS OF A FAST REACTOR. Iowa State University of Science and Technology Ph.D., 1962 Physics, nuclear University Microfilms, Inc., Ann Arbor, Michigan SOME EFFECTS OF PU-2ltO, PU-2liL, AND PU-2lj2 ON THE PU-239 CRITICAL ÎS.SS OF A FAST REA.CTGR Frank Peter Martes, Jr. A Dissertation Submitted to the Graduate Faculty in Partial Fulfillment of The Requirements for the Degree of DOCTOR OF PHILOSOPHY Major Subject: Nuclear Engineering Approved: Signature was redacted for privacy.
    [Show full text]
  • The Physics of Nuclear Weapons
    The Physics of Nuclear Weapons While the technology behind nuclear weapons is of secondary importance to this seminar, some background is helpful when dealing with issues such as nuclear proliferation. For example, the following information will put North Korea’s uranium enrichment program in a less threatening context than has been portrayed in the mainstream media, while showing why Iran’s program is of greater concern. Those wanting more technical details on nuclear weapons can find them online, with Wikipedia’s article being a good place to start. The atomic bombs used on Hiroshima and Nagasaki were fission weapons. The nuclei of atoms consist of protons and neutrons, with the number of protons determining the element (e.g., carbon has 6 protons, while uranium has 92) and the number of neutrons determining the isotope of that element. Different isotopes of the same element have the same chemical properties, but very different nuclear properties. In particular, some isotopes tend to break apart or fission into two lighter elements, with uranium (chemical symbol U) being of particular interest. All uranium atoms have 92 protons. U-238 is the most common isotope of uranium, making up 99.3% of naturally occurring uranium. The 238 refers to the atomic weight of the isotope, which equals the total number of protons plus neutrons in its nucleus. Thus U-238 has 238 – 92 = 146 neutrons, while U-235 has 143 neutrons and makes up almost all the remaining 0.7% of naturally occurring uranium. U-234 is very rare at 0.005%, and other, even rarer isotopes exist.
    [Show full text]
  • Selection of Exception Limits for All Actinide Nuclides Based on Revised Criteria for Safe International Transport
    JAERI-Conf 2003-019 JP0450009 Selection of Exception Limits for All Actinide Nuclides Based on Revised Criteria for Safe International Transport C. LAVARENNE'*, D. MENNERDAHL', C. DEAN', N. BARTON,4 V. ROUYER', G.SERT', F. JEAN', 11RSN, BP] 7 92 262 Fontenay aux Roses, France 2EMS, Starvagen 12 - 1835 7 TABY - Sweden 3SERCO, Winfirith Technology Center, Dorchester - Dorset - DT2 8Z - UK 4Departmentfor Transport,Radioactive Materials Transport Division - 2133 Great Minster House - 76 Marsham Street - London SWIP 4D - UK SAPTUS, 77 rue des chantiers - 78000 Versailles - France Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. Additionally, the total fissile nuclide mass per consignment of excepted packages was limited in the 1996 edition of the regulations (a conveyance limit is preliminary supported in the 2003 revision). The proposed changes of the rules have to take this new control into account. The European Community (DGTREN) decided to fund a project related to this subject. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the authors of the study decided to perform calculations with different codes (MONK, MCNP, CRISTAL, SCALE) and different cross-section libraries (JEF2.2, ENDFB, JENDL, etc.). This article presents the work achieved and gives propositions of modification for the LAEA requirements for the Safe Transport of Radioactive Material related to, firstly, the list of the fissile materials, and secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials.
    [Show full text]
  • Actinides Critical Masses and the Paxton Woodcock Rule
    JP0450022 JAERI-Conf 2003-019 Actinides Critical Masses and the Paxton Woodcock Rule Dr. Jacques ANNO', Isabelle DUHAMEL 2 ,Caroline LAVARENNE 3 Matthieu DULUC4 1,23 : Institut de Radioprotectionet de Sfiretj Nucljaire IRSN, BP 17, 92262 Fontenay aux Roses Cidex, France. 4 Nuclear Engineer Student at INSTY (InstitutNational des Sciences et Techniques Nucliaires)Saclay. This paper presents recent actinides (reflected or not, moderated or not) critical masses calculations performed by the French standard route (APOLLO2 Sn 8 P3, 20 energy groups cross-section collapsed from 172 energy groups CEA 93 library). Comparisons are also presented against more accurate routes of the French criticality package CRISTAL, showing the fair conservatism of the standard values. Checks of the Paxton Woodcock rule for transportation exemption limit were also made. 1. Introduction Reflectors commonly used for criticality assessments are 20 cm of water (W), 30 cm of Stainless Steel For advanced fuels reprocessing or (SS), the pair of 25 cm of lead plus 20 cm of water improvement in transport regulations, the critical (LW), 60 cm of usual concrete (density p = 23 masses of actinides are needed. Studies are being g/CM3 , H = 13740 1022, 0 = 45908 1022 , Na = performed by many organizations or groups of 2.7780 102 ', Al = 17380 10", Si = 16608 1022, Ca = experts, for example respectively JAERI 1,2) or 1.4989 1021, at/CM3). ANS/ANSI 8.15 3) . Note that the concrete composition is the standard In ICNC'99, some results of the French IRSN one, but more efficient concretes exist 9) contribution 4) to ANS/ANSI 8.15 were published, depending on the water amount especially recalling characteristics of 34 Actinides The lead/water pair reflexion (25cm/20cm and average nominal production (g/t) of 30 of them lead/water) is a standard IRSN one, but some (in PWR, BWR, UOX or MOX fuels burnt up to 35 arrangements of these two materials can also be 10) GWd/t, with a specific power of 35 W/g and 90 more efficient days of cooling time).
    [Show full text]
  • Conditions for Criticality by Uranium Deposition in Water-Saturated Geological Formations
    UC Berkeley UC Berkeley Previously Published Works Title Conditions for criticality by uranium deposition in water-saturated geological formations Permalink https://escholarship.org/uc/item/8zf4q0jm Journal Journal of Nuclear Science and Technology, 52(3) ISSN 0022-3131 Authors Liu, X Ahn, J Hirano, F Publication Date 2015 DOI 10.1080/00223131.2014.953616 License https://creativecommons.org/licenses/by-nc-nd/4.0/ 4.0 Peer reviewed eScholarship.org Powered by the California Digital Library University of California This article was downloaded by: [Joonhong Ahn] On: 05 September 2014, At: 07:37 Publisher: Taylor & Francis Informa Ltd Registered in England and Wales Registered Number: 1072954 Registered office: Mortimer House, 37-41 Mortimer Street, London W1T 3JH, UK Journal of Nuclear Science and Technology Publication details, including instructions for authors and subscription information: http://www.tandfonline.com/loi/tnst20 Conditions for criticality by uranium deposition in water-saturated geological formations Xudong Liua, Joonhong Ahna & Fumio Hiranob a Department of Nuclear Engineering, University of California at Berkeley, Berkeley, CA 94720-1730, USA b Japan Atomic Energy Agency, Geological Isolation Research and Development Directorate, Tokai-mura, Ibaraki 319-1194, Japan Published online: 03 Sep 2014. To cite this article: Xudong Liu, Joonhong Ahn & Fumio Hirano (2014): Conditions for criticality by uranium deposition in water-saturated geological formations, Journal of Nuclear Science and Technology, DOI: 10.1080/00223131.2014.953616 To link to this article: http://dx.doi.org/10.1080/00223131.2014.953616 PLEASE SCROLL DOWN FOR ARTICLE Taylor & Francis makes every effort to ensure the accuracy of all the information (the “Content”) contained in the publications on our platform.
    [Show full text]
  • Benchmark Critical Experiments of Uranium-233 Spheres Surrounded by Uranium-235
    LA-UR-94-3270 Benchmark Critical Experiments of Uranium-233 Spheres Surrounded by Uranium-235 Los Alamos National Laboratory is operated by the University of California for the United States Department of Energy under contract W-7405-ENG-36. This work was supported by the US Department of Defense, Army Strategic Defense Command. An Affirmative Action/Equal Opportunity Employer This report was prepared as an account of work sponsored by an agency of the United States Government. Neither The Regents of the University of California, the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by The Regents of the University of California, the United States Government, or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of The Regents of the University of California, the United States Government, or any agency thereof. LA-UR-94-3270 Issued: 1995 Benchmark Critical Experiments of Uranium-233 Spheres Surrounded by Uranium-235 Roger W. Brewer NEA/NSC/DOC(95)03/V Volume V U233-MET-FAST-002 BENCHMARK CRITICAL EXPERIMENTS OF URANIUM-233 SPHERES SURROUNDED BY URANIUM-235 Evaluator Roger W. Brewer Los Alamos National Laboratory Internal Reviewer Stuart G.
    [Show full text]
  • Simple Calculation of the Critical Mass for Highly Enriched Uranium and Plutonium-239 Christopher F
    Simple calculation of the critical mass for highly enriched uranium and plutonium-239 Christopher F. Chyba, and Caroline R. Milne Citation: American Journal of Physics 82, 977 (2014); doi: 10.1119/1.4885379 View online: https://doi.org/10.1119/1.4885379 View Table of Contents: https://aapt.scitation.org/toc/ajp/82/10 Published by the American Association of Physics Teachers ARTICLES YOU MAY BE INTERESTED IN Heisenberg and the critical mass American Journal of Physics 70, 911 (2002); https://doi.org/10.1119/1.1495409 Note on the minimum critical mass for a tamped fission bomb core American Journal of Physics 83, 969 (2015); https://doi.org/10.1119/1.4931721 Arthur Compton’s 1941 Report on explosive fission of U-235: A look at the physics American Journal of Physics 75, 1065 (2007); https://doi.org/10.1119/1.2785193 A brief primer on tamped fission-bomb cores American Journal of Physics 77, 730 (2009); https://doi.org/10.1119/1.3125008 fissioncore: A desktop-computer simulation of a fission-bomb core American Journal of Physics 82, 972 (2014); https://doi.org/10.1119/1.4894165 Estimate of the critical mass of a fissionable isotope American Journal of Physics 58, 363 (1990); https://doi.org/10.1119/1.16172 Simple calculation of the critical mass for highly enriched uranium and plutonium-239 Christopher F. Chybaa) Department of Astrophysical Sciences and Woodrow Wilson School of Public and International Affairs, Princeton University, Princeton, New Jersey 08544 Caroline R. Milneb) Woodrow Wilson School of Public and International Affairs, Princeton University, Princeton, New Jersey 08544 (Received 10 December 2013; accepted 13 June 2014) The correct calculation of and values for the critical mass of uranium or plutonium necessary for a nuclear fission weapon have long been understood and publicly available.
    [Show full text]